Xiaojie Wang

ORCID: 0000-0003-4290-7703
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About
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Research Areas
  • Magnetic confinement fusion research
  • Gyrotron and Vacuum Electronics Research
  • Particle accelerators and beam dynamics
  • Ionosphere and magnetosphere dynamics
  • Laser-Plasma Interactions and Diagnostics
  • Thermal Analysis in Power Transmission
  • Power Systems and Technologies
  • Microwave Engineering and Waveguides
  • Fusion materials and technologies
  • Superconducting Materials and Applications
  • Nuclear reactor physics and engineering
  • Electromagnetic Simulation and Numerical Methods
  • Pulsed Power Technology Applications
  • High-Voltage Power Transmission Systems

Chinese Academy of Sciences
2014-2025

Hefei Institutes of Physical Science
2024-2025

Institute of Plasma Physics
2014-2024

Mastering nuclear fusion, which is an abundant, safe, and environmentally competitive energy, a great challenge for humanity. Tokamak represents one of the most promising paths toward controlled fusion. Obtaining high-performance, steady-state, long-pulse plasma regime remains critical issue. Recently, big breakthrough in steady-state operation was made on Experimental Advanced Superconducting (EAST). A with world-record pulse length 1056 s obtained, where density divertor peak heat flux...

10.1126/sciadv.abq5273 article EN cc-by-nc Science Advances 2023-01-06

During the high-power long-pulse operation of gyrotron, radio frequency (RF) oscillation faults may occur, which can affect stable electron cyclotron resonance heating system. Recently, some research has begun to use deep learning diagnose RF in gyrotron. However, these learning-based methods have overlooked useless or erroneous data, we refer as noisy gyrotron experiment data. Noisy data are inevitably generated during acquisition process, would lead performance degradation methods. To...

10.1063/5.0257521 article EN cc-by-nc-nd AIP Advances 2025-03-01

A 140GHz electron cyclotron resonance heating and current drive (EC H&CD) project for EAST Tokamak is launched in 2011 with a total power of 4MW pulse length 100 s. The main objectives the system are to provide central H&CD, assist start-up control MHD activities. comprises four gyrotrons each nominal output 1MW at 140GHz. RF power, transmitted through evacuated corrugated waveguides will be injected into plasma from low field side (radial port). front steering equatorial launcher directs...

10.1063/1.4864607 article EN AIP conference proceedings 2014-01-01

This paper presents a stable millimeter-wave power monitoring system for ECRH on EAST tokamak. The real-time was realized based monitor miter bends. "Exchange"method proposed to the reflection RF protection. A cRIO-based signal process unit designed, it is robust and has response time of 1 μs. tested experimental results were discussed.

10.1109/access.2016.2611618 article EN cc-by-nc-nd IEEE Access 2016-01-01

Gyrotrons are vacuum electronic devices capable of generating high-power, high-frequency THz radiation. With the increasing utilization gyrotrons in thermonuclear fusion experimental devices, achieving higher output performance and ensuring stable reliable operation have become key development goals. However, occasional radio frequency (RF) oscillation faults inside gyrotron during long-pulse hinder its operation. Due to difficulty directly observing abnormal changes within resonator...

10.1063/5.0195400 article EN cc-by AIP Advances 2024-04-01

High-k turbulence (1 < kθρs 5) spectrograms have been directly measured in density modulation experiments of the EAST tokamak using collective Thomson scattering diagnostic system. Density-peaking is achieved Lower Hybrid Wave (LHW) experiments, revealing that broadband sensitive to power LHW and concomitant variation density-peaking. Additionally, contributions 2.45/4.6 GHz peaking differ when Neutral Beam Injection (NBI) on/off, displaying distinct responses low/high frequency...

10.1063/5.0197005 article EN cc-by AIP Advances 2024-06-01

Abstract I-mode is a promising regime for future fusion reactors due to the high energy confinement and moderate particle confinement. However, effect of lithium, which has been widely applied recycling impurity control, on plasma still unclear. Recently, experiments real-time lithium powder injection have carried out in EAST Tokamak. It was found that performance can be improved by injection, strongly reduce electron turbulence (ET) then trigger ion (IT). Four different regimes identified...

10.1088/1741-4326/ad80a8 article EN cc-by Nuclear Fusion 2024-09-27
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